DE1439840A1 - Heavy water moderated organic refrigerated cracking reactor and process for its operation - Google Patents

Description

United States Atomic Energy Commission, G-ermantown, Maryland / USA.

Heavy water moderated organic cooled nuclear fission reactor and procedures for its operation

The invention "relates to a heavy water moderated, Nuclear fission reactor cooled with an organic liquid with reduced requirements to reactivity »

In particular in recent times new efforts have been made in reactor technology To find new ways and in this way to develop new energy sources with reduced costs can, which are also competitive with the conventional power plants that used fossil fuels are. Considerable progress has now been made in this direction, but it must nonetheless nuclear energy is still struggling with the various types of energy production that have been customary up to now »Exceptions are only found in particular geographical

809807/0221

143984C

-2 - .'- ■■■■ '. - V ■■ '■; ■■

location or under special conditions, as it is "with-" for example in remote areas, in for whom the cost of supplying fuel is excessively high »

In order to further improve the efficiency of nuclear reactors, we are constantly working on finding substances which, when used in a reactor, provide an optimal degree of efficiency, and in reactor construction, too, new ways are constantly being explored in order to really get these substances in the best possible and most effective way to use. For example, one of the best moderator substances that can be used for thermal reactants is heavy waste. ; ^ ^Γ ~ ύΛ ~) _), which has a smaller absorption cross-section for IT / - '^ tq-on than almost all other substances. Since it, a further is a liquid, it can be readily used _. and circulate. In view of its very high vapor pressure, however, it must be used at a relatively low pressure if the costs for the high-pressure equipment required are not to be excessively high should that only a small amount of this substance is needed. : -: -:,: -.- ...

BATH

80 9807/0 2 2

One way of reducing the required amount of heavy water (D ₂ O) is to limit the use of this liquid to its function as a moderator and to use another liquid with a low vapor pressure as a coolant. Although there are a number of coolants available for reactor technology that meet these requirements, there are relatively few substances with corresponding core properties that are effective at relatively low pressure values with a corresponding heat transfer level and at the same time do not cause any undesirable difficulties in handling. At higher pressures it is possible to carry out the heat transfer more efficiently, but the gains achieved thereby are due to the higher output; and. Maintenance costs for the high-pressure systems in the entire power plant have been lifted. From liquid. Metal coolants, which can be used at low pressure, have the disadvantage that this results in a number of problems that are difficult to solve, -these ... again only by using extremely complex systems and after overcoming them "A multitude of different operational difficulties can be solved", but substances that have met with great interest in reactor technology as coolants that can be used at relatively low pressure are organic liquids, for example

BATH ORIGINAL

. * -: ■?! $ = # 3 GAS

8 0 9 8 0 7/0221

Terphenyl.

Apart from the separation of the cooling and moderator functions in a reactor ordered another way to "reduce." the size of the heavy water systems and facilities therein, the reactivity losses in the reactor to belittle. ITm to illustrate the savings that can be achieved Achieving a slight increase in reactivity of a nuclear reactor of the type and size described in detail below means a 40% increase in costs what is required for the heavy water system is «So if a nuclear reactor is to be created, at used in heavy water with an optimal degree of efficiency the reactor must be designed in such a way that the reactivity losses are further reduced, than was previously required for nuclear reactors to generate energy on a larger scale Greatness has never been possible before.

Another for a practical and efficient reactor the most desirable feature would be the possibility of being both natural and natural also use slightly enriched uranium as fuel. Because this is an optional possibility is given, the energy output can be without costly Conversions can easily be improved by simply

8 09 80 7/02 2

in each case with regard to delivery and costs the most favorable fuel supply can be exploited.

The invention now relates to a reactor and a method for its operation, can be used in the first heavy water so effectively, as far in power reactors was never possible _o The efficiency of such power plants is thus increased so that Energy can be supplied at a cost that is significantly more competitive than the previous energy sources «In addition, according to the invention, either natural or slightly enriched uranium can be used as fuel without the reactor having to be modified in any way.

As is well known, sufficient excess reactivity is provided in the construction of nuclear reactors for the purpose of around for certain foreseeable losses, reactivity changes during the life of the reactor and uneven Meutron flux in the core to create a balance and thus to ensure that during the Design life of the reactor there is always sufficient reactivity to maintain the desired operating level. The various reactivity losses can generally be broken down into the following Classify groups:

809807/0221

1. Parasitic neutron absorption in the the coolant, enveloping metal Construction parts,

2. neutrons captured by the Hegel's rods and

"3. Neutron losses as a result of increasing Leak phenomena j / which are due to the fact that the total energy distribution becomes flatter at the core »

The neutron losses of the first group can largely are reduced by the fact that the planning from the thermal-hydraulic and mechanical point of view carefully thought out and at the same time attention is paid to the lowest possible energy costs, so far this can be reconciled with the requirements of nuclear technology. The reduction of the neutron losses second and third groups, on the other hand, are more difficult Problem posed in specialist circles since worked for a long time *

To increase the heat output of a reactor is generally proceeded in such a way that the This flattens radial energy distribution in the core becomes that the fissile material in the radial direction differentially charged and thus the neutron flux in the the central area of the core is made flatter. However, this goal causes a loss of reactivity, because this increases the possibility of neutron

8 0 9807/0221

Leok losses increased. It can also burn out stationary fuel in the higher flow range in the center of the core shows an energy flattening with a corresponding loss of reactivity as a result of increased leakage losses cause. In the case of a heavy water reactor designed for operation with natural uranium fuel, if a critical system is to be maintained, any loss of reactivity can only be compensated for by either additionally DgO added or the design service life « i.e. the burning time of the fuel is set to be shorter. Affect both hatreds however, the profitability of such a system is quite considerable »

According to the invention, there is a substantial reduction in the through the use of control rods and the course neutron losses due to the neutron flux through the nucleus achieved to an extent as has been achieved so far for power nuclear reactors with a low-pressure coolant For example, an organic liquid, and a moderator consisting of heavy water was impossible »

The idea of the invention is to create a design with a high neutron utilization without at the same time the heat output of the core is somehow impaired. A biaxial fuel

809807/0221

8th - . -: ■■ - ■ ■ - ■. -

The feed process becomes a constant radial Energy distribution achieved in the middle. High fuel channels and lower in the outer core areas is. By providing a two-way coolant flow "with the cooler inlet flow through the Middle area and the hotter, in the second run, sensitive coolant flow flows in the outer area, the limit temperature conditions are balanced to the extent that that the heat can be drawn off through a smaller number of channels.

In short, it would be said that in the case of the invention Reactor is provided with a special arrangement in which there is no excess reactivity, which needs to be controlled with steady operation. The arrangement is made such that the fuel is moved during operation of the reactor, which ensures that the total radial and axial flow and the energy distribution always remains the same as this was the case with a freshly charged core. So it works in this way no reactivity due to flattening of the central. ITeutron flux lost, ^ 'in another extraordinary feature of the invention Reactor consists in full distribution of the fuel at all burnout points in the individual Flußkanäleri, which ensures that the output power of each channel always remains constant.

BAOORfQfNAt

80 980 7/02 21 ■

Further features that complete the overall result emerge from the description below.

The invention is therefore essentially based on the object of a nuclear reactor and a method for operation to create such an Eeaktors in which the ifeutronen losses largely reduced.

For this purpose, the invention envisages one that is cooled by an organic liquid and moderated with DpO Nuclear reactor with reduced neutron loss.

According to a further feature of the invention, a nuclear reactor be created with a core where provisions are made to keep the fuel at Normally continuing reactor operation can be set in motion, removed and replaced so that the reactor was kept in operation without excess reactivity throughout its operating life will.

Further features and advantages of the invention are given below with reference to a preferred embodiment explained in more detail with reference to the drawings. Show it:

Figure 1 is a partially schematically illustrated elevation a single row of pressure pipes in

809807/022 1

- ίο -

a shown in section according to the invention Reactor;

FIG. 2 is a plan view of the reactor of FIG. 1;

Figure 3 is a schematic representation of the for this Reactor provided core assembly;

Figures 4-A, 4-B, 4-G and 4-D show a typical pressure pipe construction, partly in section, extending over the length of the reactor shown in FIG extends; -.-.- ■ -. ■ "...-

Figure 5 shows a typical fuel element assembly shown in Section is shown to show that the ends of the fuel rods are against each other are offset and

FIG. 6 shows a section along the line 6-6 in FIG.

Figures 1 and 2 show a nuclear reactor 10 with a closed cylindrical moderator container 12 with a lower inlet port 14 · and an upper outlet port 16, as well as with the upper and lower wall areas 12a and 12b, respectively. The walls of the container 12 are optionally provided with thermal shields 18, 22 and 24 "occupied at a distance from the container walls may be appropriate. Through the entire encoder container 12 runs through a plurality of at a distance mutually attached vertical coolant pipes 26, which, as described in detail below, contain the fissile fuel of the reactor 10

80 980 7/022 1

and through which the coolant flows in order to dissipate the heat generated during the cleavage. The one in the container 12 located moderator liquid flows around the tubes 26, which apart from the ■ connecting lines and the removable collectors to be described in detail below are completely sealed off are. Above and below the moderator container 12 there is an upper and lower cylindrical respectively Shielding container 28 or 32, which is partially covered with a speaking radiation-shielding material, for example iron shot 31 and 33 is filled. The coolant tubes 26 run completely through Shielding containers 28 and 32.

The arrangement consisting of moderator container 12, shielding containers 28 and 32 and coolant tubes 26 is from FIG a concrete wall 34 · enclosed by two or a plurality of brackets 36 of the upper shielding container 28, the brackets 38 for the moderator container 12 and the brackets 4-2 for the lower shielded container 32 is kept at a distance. The inlet and outlet ports 14 and 16, respectively, for the moderator are not shown Lines connected, which are guided through the recesses 44 and 46 in the concrete wall 34, so that the Moderator can be circulated outside the reactor 10 and cooled there.

BATH ORIGINAL

809 8 0 7/0221

143984G

According to one feature of the reactor according to the invention, the arrangement is such that the coolant is brought into circulation in a double passage running in two joints in order to reduce the influence of the non-uniform neutron flux intensity in the core as much as possible and to determine the thermal boundary conditions. In this way, a higher heat output is to be achieved with a given number of channels. In this embodiment, the first coolant passage is introduced into the cooling tubes located in the middle. First pass fluid is mixed in such a way that the coolant is supplied to the cooling tubes of the second pass at a uniform temperature. Adjacent tubes are connected to their respective collectors at opposite ends so Ü ^ ⁹ of. Flow in these pipes always takes place according to the countercurrent principle. In this way, a largely uniform temperature is achieved in the core area.

As can be seen in detail from FIGS. 1 and 2, and sebematically also from FIG. The coolant is supplied from a common acidic: pipe 5 ^ to the -, -

BAO

8 09 80 7/02 ZX

H3984C

upper region of the container 12 through the collector 48, the intermediate collector 84 and the transfer pipes 53 to the upper portion of the coolant tubes 26 of the first passage. The supply of fresh coolant to the lower area of the container 12 takes place via the intermediate collector 85 and not shown transfer pipes. As already has been explained above, the coolant tubes 26 located in the central region become from the first coolant passage flows through, while the pipes located in the outside area for the conduction of the second coolant passage to serve. As shown schematically in particular in Figure 3, the adjacent drilling 26 the coolant is supplied from the upper or from the lower main collector 48 and 50, respectively, so that it adjacent tubes in opposite directions Direction flows through. The upper and lower downstream ends of the tubes 26 of the first passage are via transfer tubes 54 and 56 with the intermediate collectors 82 and 86 and the main collectors 58 and 62, in which the coolant coming from the different channels is mixed in such a way that a uniform temperature is achieved. The main collectors 58 and 62 are via intermediate collectors 87 and 88 and via overhead lines 64 and 66 with opposite ends of mutually adjacent tubes 26 in the outer region of the second coolant passage tied together. At the outlet of the second passage of the tubes 26, the coolant is fed to the hatipt

. BAD ORIGINAL; v ^ O 80 980 7/02 2 1

143984G

outlet collectors 72 and 74- passed, which happens via the intermediate collector 89 and 90, in turn the individual streams mixed with one another and diverted through a common pipeline 76 and for generation of the working steam in the one containing the reactor Power plant can be used.

Another essential feature of the invention Nuclear reactor is that see the fuel in the * pipes 26 is, so that. a fuel refill in the ascending stream and a pushing of the Fuel is enabled during operation, -so that the fuel is always in at all burnout points the individual tubes 26 is completely evenly distributed and thus guaranteed. that the in radial and total flow effective in the axial direction and the energy distribution remains essentially constant so that no reactivity whatsoever due to flattening of the central neutron flux it is lost.,

For a more detailed description of a typical coolant pipe 26a refer to Figures 4-A, 4-B, 4-C and 4-D taken, each of which sections of the tube 26a demonstrate. In general, it should be noted that the tube 26a consists of an upper region 102, a middle region or Oalandria tube 104 · and a lower section 106 exists. The coolant is added to the upper region 102

8AÖ ORIGINAL

80 98 0 7/02 2 1

143984G

passed through to a transferring room 53a; this area, is sealed at the top with a cap 108 which is inserted into the thimble opening 112 of the tube 26a is screwed in. The lower region 106 has a transfer pipe 56a for the coolant that emerges from the pipe 26a. The sealing cap 108 is provided with a pin 114, a transverse pin 116 and recesses 117, with the help of which the cap 108 can be removed if necessary. As can be seen from FIG. 4B, the lower section 102 ends in FIG the upper wall 12a and the shield 24 of the moderator container 12th

In the tube 26a, a guide tube 118 is suspended from a threaded flange 122, which in turn is supported by the Outer wall of the tube 26a is at a distance and through Spacers 124 is kept at this distance. The guide tube 118 has a row as shown larger recesses 126, which the coolant can freely flow around or through.

As FIG. 4B illustrates, an internal pressure tube 128 is exposed at the lower end of the guide tube 118 a flange 132 held, which in turn in the upper Area 102 is screwed in. With a very small gap there is one directly around the internal pressure pipe 128 below the upper wall of the moderator

809807/022 1

A Calandria tube protruding from the container 12 104 lying around that on the. upper shield 24 fastened in any way, for example by welding and passed through the moderator container "12" between the pressure pipe 128 and the Calandria drill 104 The intermediate space is located via the pipes 1J6 and 138 with the aid of a sealing arrangement 139 pressurized with an inert gas, taking care that there is no moderator in the coolant or coolant can get into the moderator o The Galandria tube 104 ends in a similar manner in the lower wall 12b of the moderator container 12, while the lower end 141 of the internal pressure tube 128 is below the moderator container 12. Two pipes 142 and 144 with a corresponding sealing arrangement 146 also cause a corresponding seal in the manner described above.

The outlet guide tube extends from a point in the vicinity of the end 141 of the internal pressure tube 128 151 down to a threaded flange in the lower thimble-like component 1-4 of the coolant pipe 26a. One with a longitudinal pin 158 and one transverse pin 162 engaging therein, as well as with a thread the sealing cap I56 closes the cooling pipe 26a sealing at the bottom.

BATH ORIGINAL

80 9807/02 21

In the tube 26a extending between the upper and lower sealing caps 108 and 156, respectively a solid rod 164 with parts 166 serving to adjust the fuel and for spacing purposes and 168 for fixed interlocking with the guide tubes 118 and 151. Two cross pins 1? 2 and 174- facilitate this the attachment when removing or reinserting. The stick 164- carries only a few when touched Burning charges I76 in the moderator container 12 and is about his Length in various places with spacers 178 provided, with the help of which the rod 164- always correct is kept centered. As can be seen, in the arrangement shown and described above, burning sets 176 without further ado, simply by doing both Sides are pushed out of the tube 26a, the end caps 108 and 156 removed and the rod 164- pulled or is pushed.

Details of a typical burner assembly 176 are shown in FIG Figures 5 and 6 shown. The burning set I76 consists from a bundle of fuel rods 192, which differ from one another by two different diameter values; these rods of different thicknesses are labeled 192 'and 192 ", respectively. These rods are formed into a circular shape Bundles combined and held together by die.Bänder 201. According to the representation of the figures 4-B and 4-C are five such sets I76 axially im

809807/0221

Pressure pipe 128 arranged. The ends of the fuel rods 192 are offset from one another as shown in FIG. 5, so that the fuel losses caused by the end caps are not concentrated in a small area at the end of a fuel assembly. This reduces the formation of river peaks. The outer ring-forming fuel elements 192 are, however, all have the same length, so that the fuel element sets concurrent according to their composition and balanced bearing surfaces, as is also apparent from the figures 4B and UG ₀

The fuel rods 192 each consist of UCU} the with a tube 202 is lined with one spiral extending rib 204- formed in one piece by extrusion is. The ends of the tubes 202 are closed by the end caps 205. The rib 204. Serves the Tie the bundle 176 together as a spacer between the individual fuel rods 192.

It should be noted that the burning sets 176 without actual Intermediate connections only lie directly next to one another, as is the case with the rod 164- and the end burning charges I76 is the case »Because there are no connecting wires in the core, the parasitic neutron absorption is reduced. The adjustment rods 164 are used for the fuel

- bath
80980 7/022 1

only as a spacer to maintain the correct position of the burning sets and also enable them Removal as will become clear below in detail.

The device used to control the reactor has not been described, but even without this it should be evident that control rods are inserted between the coolant tubes in the moderator and the control can be carried out in the generally known manner consists of the so-called Hy-Ball control, in which columns formed from borated steel balls are introduced into the moderator container 12. With the aid of hydraulic means, these balls are pumped into the moderator area of the reactor and removed from it again. The following table only refers to this type of "poisoning regulation, but of course any means can be used for this purpose , since these means are not essential to the invention.

When the reactor described above is in operation, fuel assemblies can be charged without the power plant having to be shut down for this purpose. It is easy to do this, the 'two ends of a cooling tube 26 by removing the sealing caps at regular intervals.

bath

809807/0 22

stood open. Then the spacer bar serves 164- to this, the fuel assemblies 176 in the direction of the coolant flow far to move ,,. "to, in the typical case,. a set can be taken from the downstream end. Then on the upstream side, i.e. on other end of the cooling tube, a fresh fuel under corresponding handling of the rod 164 is used. So the hottest coolant is at the end of the Channel in contact with the fuel that generates the least energy in the channel, so that there is a more effective thermal utilization.

So it is that during the entire lifetime of the reactor as soon as it is commissioned waiting time has expired, in each channel over its entire length and during its entire Operating time is essentially a constant fuel composition, so that the radial and axial flow and energy distribution not changed over time. This way there is no reactivity lost by the flattening of the central neutron flux, as is the case with reactors of the hitherto customary design the EaIl is.

This method of fuel handling brings in Maximum requirements in terms of reactivity;, um when "using the in the following"! a-belle.be-

BATH ORIGINAL

8 0 9807/0221

to create a degree of utilization of 5000 with natural uranium. So it will be with this one Type of fuel loading the nuclear advantage of the lowest possible reactivity requirement without any burden achieved a high output for the thermal-hydraulic design.

Another advantage of the method according to the invention for inserting fresh fuel assemblies becomes clear, if a fuel use Ms 20 000 MWD / iD with Enriched fuel is considered. Fuel that has to be discharged from the reactor, Experience shows that the entire gap cross-section is greatly reduced compared to the freshly charged one Fuel on * Since every river channel at all burning points contains a complete fuel distribution, the energy output of the individual channels always remains constant. The thermal design does not need to be such that it takes into account the use of both natural and enriched uranium highly variable energy levels in the individual Channels. To the extent that the fuel elements pass through the channel, as a result of ■ Due to the increasing burnout, the local energy production in the element may be lower. aside from that is due to the fact that the reactor is continuously charged with new fuel without it being shut down for this purpose.

809807/0221

to be laid "needs" the entire shutdown period of the reactor compared to the shutdown time required for the previously known reactors reduced, whereby the utilization or efficiency of the reactor as an energy source .ganz substantially elevated.

The parameters of a reactor design: for one according to the invention Systems in the order of 5QQ MWe (both with natural and slightly enriched fuel) are given in the table below.

So it was created with the invention, a nuclear reactor in which a heavy water moderator more effective Use is made than previously thought possible and at the same time also other advantages including a higher degree of utilization of the Fuel and reduced neutron losses.

• WELSt. /"..- "..

Incidentally, only one has been preferred above. Embodiment of the invention described and, the scope of the invention is of course not limited to this one embodiment, but includes * also numerous "changes" without exceeding the scope of the invention.

809807/0221

Tabel All of it

Reactor type

Type of steam circulation

total fissure energy including moderator heat losses, Mw

total electrical energy output of the turbine, MWe

Hetto electrical energy output of the system, HWe

Net heat output of the system, Btu / kw-hr

Net efficiency of the system, %

DpO - moderated, organically cooled

without reheating with liquid removal from the turbine

1550

542.3

enriched 512.2 of course 510.3

enriched 10 of course 10

enriched 33 »05 of course 32.92

Fuel and core

Type of fuel

Fuel density,% of theoretical

Combustion design, Mwd / t enriched 20,000

of course 5

Wrapping material Envelope thickness, mm

Fuel rod (outer diameter 7.9502 and 13.0302), mm

XAP-001

and 0.464

809807/022

..- 24 -

Number of fuel rods per bundle

Total length of the fuel bundle ^ cm

Number of bundles per pressure pipe

Number of coolant tubes

Grid arrangement division cm material

Outside diameter 5 cm wall thickness ₉ mm insulation material

Core length, cm 6 plus 31 101 _s 60 5

600 'square

Zr-2 and XAP-OOI 'Zr-2 s 0.91441 XAPs 1 _S 5748

Inert gas inlet zone with 2 _? 5> 4 mm

■ 487.6a- ..

Equivalent core diameter - 683 _s diameter, cm

Radial reflector - 30.48 thick, cm

Axial reflector - 30 ₅ 48. thick, cm

Total UO ^ filling kg 111

Tjp of the rule unit Hy-ball number of control units

core

enriched

Naturally

Reactivity Tolerances 3 %

Cold too hot, Hodera- -O ₈ 26 tor to 93 ₉ 33 ° ^G coolant - + 0.85 to 343.3 ^Q C -0 ₅ 26 4-1.1

BATH ORIGINAL

809807/022

Zero Ms full lei- -0.54 -0.54

stung (Doppler)

Cold Ms equals -3.2 -3.3

weighting status,

Xenon, samarium

Burn-off (first core 0 - ^ yI

top to balance)

Maximum "excess response - 4.0 5.8

activity, f '

Total reactivity 10 ■ '11 (worth of Hy-balls),

Decommissioning leeway 6 5

Coolant temperature 3.5 χ 10 ^J 4 χ 10 ^ reactivity coefficient,

Fuel temperature- -0.6 χ 10 - ^ -0.6 χ reactivity coefficient
(Doppler), δ

Moderator temperature -2 χ 10 "- ⁷ -2 χ 1θ" Eeactivity coefficient,

Fuel use and burnup

Total uranium, t 98.7 - 98.7

Initial enrichment, - 1.25 0.7115

w / o u-235

Final enrichment, 0.50 O ₄ 30

- w / o U-235

subtracted plutonium, 6.09 3.23

g / kgU initially

Design life 20,000 5,000

duration, MWD / t U

809807/022

Fuel conversion ratio,. (Weight *) Total service life '-

Total Pu.- 1.40 1 _} 24 "

Amount / over 235 losses

Fissile Pu Produce 1.23. 1.06

gung / U-235 losses

Usable life, 0.51 0.79

remaining Pu / U-.

235 losses,

Energy generation over the lifetime, ° / o

Ii-235 cleavage 0.49 0.64

U-23S Sclanell Cleavage 0.01 0.01

Pu cleavage 0.50 0.35

ühermiscne

Mean heat flow, 115 000 115 Btu / nr ft ² -; ~ r ·

Maximum heat flow.,. 298 400 ^: 352 Btu / nr ft ²

River or heat generation conditions, maximum / average

Basic ratio radial 1 _S 35 1 ₅ 96

Basic ratio axial 1 _s 60. 1.29

Radial local 1.05; 1 _s 0?

Axial local 1 _s 04 _; '.'. 1 _? 03 ■

Maximum temperature of the < 454 <454

clad JB ¹ IaClIe ₅ ⁰ O -

Maximum UQ ^ -Br enns to ff- <1898 «C2063

Temperature including ₀
Peak load point factor 3 "

Minimum «= DNB-Yer] age > 4.8

809807/0221

Primary coolant syst em

Coolant Santowax OMP, 10% high boiling point Substances

Total coolant flow, 19 »446.140 kg / h

Energy supplied to the coolant, KW 1 480

Reactor temperature Eingangstempe- 280, ⁰ O

Reactor exit temperature- 404 rature, ° 0

i Temperature rise through 106 reactor, ⁰ O

Total pressure drop in the enriched 267 system, of course 305

Enriched reactor pressure drop 223 (From collector to collector - of course 259 ler), psi

Number of turns 4

Type of pumps Centrifugal pumps

Number of pumps per 1 turn

Coolant pressure at 80 pump inlet, psia

Pump outlet pressure, psia enriched 347

of course 383

Pump energy per enriched 3 pump, KWe of course 4

Coolant requirement, kg 358 100 reprocessing kg / day 3263 Inert gas nitrogen

with the coolant to carbon steel, XAP-OO1,

Contacted work- stainless steel

fabrics

BATH ORIGINAL

8098 0 7/022 1

Moderator system

Medium. D ₂ O Moderator container
leaving temperature, ⁰ C 54 Moderator container
outlet temperature, ⁰ C 87 Design temperature 121 Total throughput, kg / h 1 -971 800 Number of turns 1 Number of pumps per
Twist 1 Pump type Centrifugal

Pump head pressure at 50 nominal flow rate, psi

Pump output per pump, kw

System design pressure, psig

Inert gas

Hit the moderator Materials in contact Total requirement, kg Processing,, ig / lag Cooling

300

150

helium

stainless steel, zircaloy

235 157 2268

ITicht-regon e i? At iv

Secondary oyster .;

u3JHi.'i - ':' Gr.ifcr & .Gor-j -.-: '. K-

193

BAD OR (QiNAt

Steam generator outlet 273 temperature, ° 0

Überhitzereinlaßtempe- temperature 273, ⁰ O

Superheater outlet temperature- 385 rature, ° 0

Steam generator pressure, psia 850

Superheater outlet pressure, 825 psia

Steam generator throughput 2 320 kg / h

Steam flow to turbine, 2 307

High pressure turbine inlet 385 1ass temperature, ⁰ O

High pressure turbine inlet 800 pressure, psia

Intermediate pressure turbine 24-3 inlet temperature, ° 0

Intermediate pressure turbine 240 inlet pressure, psia

Low pressure turbine inlet temperature, ⁰ C

Low pressure turbine inlet 58
pressure, psia

Condenser pressure, inches 1.5 Hg

Number of feed water 5
preheating levels

Centrifugal feed pump type Number of pumps 2

Pump output per 3 pumps, kw

Pump pressure, psi 1

J / ■■■■. · 809807/0221

Claims (7)

Claims 1. Nuclear reactor having an elongated bore consisting of a plurality of fuel containing Reactor core accessible from both sides, moderated with heavy water and an organic one Liquid is cooled, characterized in that each tube in each case in all stages of the burnout contains located fuel assemblies and adjacent tubes each from opposite ends with Fuel supplied so that a flat radial and axial general distribution of the neutron flux and the energy is sustained. 2. Nuclear reactor according to claim 1, characterized in that means are provided with the help of which the coolant is supplied to the coolant pipes close to one end and discharged close to the other end, the arrangement being made such that the cooling medium flow in adjacent pipes takes place in opposite directions. _x 3. Nuclear reactor according to claim 2, characterized in that; marked, that means are provided by means of which the coolant has two complete passages through the pipes is passed through, the first passage 'through 'coolant pipes lying in the middle area of the core 80 98 0 7/0 221 follows, and the second coolant passage through the remaining, takes place in the outer area of the core tubes, so that overall more uniform temperatures in the Core area are preserved. . 4. Nuclear reactor according to claim 3, characterized in that that the "located in the individual coolant pipes" Fuel sets are each arranged in such a way that the freshest fuel on the upstream end of the Coolant pipe "and each following downstream Fuel set has already been used up further than his each upstream adjacent fuel set. 5. Nuclear reactor according to claim 4, characterized in that two first semicircular main collector are placed around the upper and lower part of the moderator container and serve to receive fresh coolant, means for distributing the coolant are provided in the collectors of the coolant tubes, that two annular collectors at the top and bottom of the tubes and for mixing at the end of the first pass ίίΐτΐοΐ for distribution. des _>: coolant on. .the ring-shaped Sarraler .are provided ,, that so ^. ^ eniise'ite. ΙΙ ", ι ·: 1.αί. ': ~; Ο1 in' lie K.'ilil-: iittelrohrc des nweit Durcr. ^ I ^ ec. Introduced v; iro and dajj .. 7AJC L, wqi.-jp.rG HalbkrelrJ'-jr ^ ii ^ e .ilauptsai-val ';:. · voj: ~ are seen ·, .jd.i, e. , den.;, both ersuen halrlcreiafcr.ui ^ u :; rlr uptsa.ni:ilcrn are arranged opposite and which 'read ORIGINAL BATHROOM 809807/022 heated coolant is fed, with which the second Passage through the reactor is complete, and that the heated coolant is diverted for external utilization, will. . 6. A method for operating a nuclear reactor whose fuel is arranged in a plurality of spaced apart channels through which a coolant is circulated, characterized in that the coolant is pumped through in opposite directions in adjacent channels, that the coolant of the first passage pumped through located in the central region of the reactor channels, and the coolant of the two ^"! th passage through located in the outer region of the reactor channels, and that the fuel is switched during normal reactor operation at regular time intervals to the radial and axial general ^ leutronenfluß and to keep the energy distribution essentially the same over the life of the reactor. "- ', ..,. , 7. The method of claim 6, wherein the fuel of each channel is axially disposed with no body attachment Summaries consists, characterized in that a fuel set is exchanged in a channel in the manner that the fuel from the downstream Pushed out at the end of the respective canal and an unused one at the upstream end of the canal Burning charge is used. BATH